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MONTHYEARML20213F1241986-11-0707 November 1986
Concurs W/Intent of Amend 108 to License DPR-16,revising Radiological Effluent Tech Specs,Per 10CFR50,App I.Exception Taken to Basis 3.6.A (SEP Topic XV-16) Re Radiological Consequences
Project stage: Other
ML20211M3851986-11-28028 November 1986
Forwards SER Re Util 850726 Request for Deferment of Eight NRC Required Mods from Cycle 11 Refueling Outage to Either Cycle 11 or 12R Outage.Request Acceptable for Deferral to Cycle 11,but No Later than Restart from Cycle 12R
Project stage: Approval
ML20148G4931988-01-19019 January 1988
Requests Addl Info Re Implementation of ATWS Rule Requirements,Including Provision of Electrical Functional Diagrams for ARI & RPT Sys from Sensors to Final Actuated Devices,By 880210
Project stage: Other
ML20195K0201988-01-22022 January 1988
Requests Addl Info Re Util 831114 & 851023 Submittals for Generic Ltr 83-28,Item 2.2 (Part 1) Re Equipment Classification Program (Programs for All Other safety- Related Components).Response Requested by 880229
Project stage: Other
ML20149L6291988-02-18018 February 1988
Forwards Safety Evaluation Supporting Proposed Design for Standby Liquid Control Sys.Tech Spec Change Request Needed by 880331
Project stage: Approval
ML20205L0091988-07-31031 July 1988
Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept
Project stage: Other
ML20205K9921988-10-21021 October 1988
Forwards EGG-NTA-7293, Conformance to Generic Ltr 83-28, Item 2.2.1-Equipment Classification for All Other Safety- Related Components:Oyster Creek, Accepting Util 831111, 851023 & 880518 Responses
Project stage: Other
ML20205P5231988-11-0404 November 1988
Forwards Safety Evaluation Supporting Util Submittal Re Compliance W/Atws Rule 10CFR50.62 Concerning Alternate Rod Injection & Recirculation Pump Trip Sys.Design Does Not Meet Requirements of ATWS Rule & Not Acceptable
Project stage: Approval
ML20235H7431989-02-16016 February 1989
Advises That Util 890120,23 & 31 Ltrs Re IGSCC Insp & Repairs Performed During 12R Refueling Outage Meet Generic Ltr 88-01 Requirements.Safety Evaluation Will Be Sent Under Separate Conver
Project stage: Approval
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
Project stage: Meeting
ML20058K5061990-06-28028 June 1990
Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved
Project stage: Approval
ML20058A6381990-10-18018 October 1990
Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01
Project stage: Approval
ML20073H5581991-04-24024 April 1991
Discusses Alternative Method of Monitoring Containment high- Range Radiation Monitors,Per Amend 116 to License DPR-16. Justification Provided to Support Conclusions That Addl Preplanned Monitoring of Monitors Unwarranted
Project stage: Other
RA-09-017, Letter from Exelon, Subj: Request for Exemption from 10 CFR 50, Fire Protection of Safe Shutdown Capability2009-03-0303 March 2009
Letter from Exelon, Subj: Request for Exemption from 10 CFR 50, Fire Protection of Safe Shutdown Capability
Project stage: Request
1988-02-18
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Text
70 W htute of Nelu 5tratg m
DEPARTMENT OF ENVIRONMENTAL PROTECTION y
DIVISION OF ENVIRONMENTAL QUALITY BUREAU OF NUCLEAR ENGINEERING CN 411 TRENTON, NEW JERSEY 08625 (609) 530-4022 November 7, 1986 Mr. John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Zwolinski:
SUBJECT:
LICENSE AMENDMENT NO. 108 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION (MPA A-02, TSCR 69, TAC 08100)
Re:
Oyster Creek Nuclear Generating Station The Bureau staff reviewing this license amendment has advised me that we have concurred with the intent of Amendment No. 108, which authorizes changes to Appendix A technical specifications to incorporate the Radiological Effluent Technical Specifications (RETS) required by 10CFR50 Appendix I.
They do however, take exception to Basis 3.6.A (SEP Topic XV-16: Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Activity Outside Containment) as it impacts on federal regulations, i.e. 10CFR100. As they have discussed with Mr.
Donohew by telephone, my staff has specific concerns with the licensee's ability te mitigate this type of accident due to the unique desige of Oyster Creek.
I understand that this component has been eliminated from this licensing action and will be addressed separately in license No. DPR-16 (Postulated High Energy Line Break within Emergency Condenser Penetrations).
Mr. Tosch has asked me to request more technical information on SEP Topic XV-16, i.e. the essumptions on which the Safety Evaluation Report's conclusions were based.
If you should have any questions, please contact Mr. Kent Tosch, of my staff, at (609) 530-4022.
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Thank you.
1 0 Very truly yours,
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8611140022 861107 PDR ADOCK 0500 9
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David'M. Scott, Chief Bureau of Nuclear Engineering pOb cc: Gerald P. Nicholls, Ph.D.
Jack Donohew, NRR A0 b',
Kent Tosch